ML12150A367
| ML12150A367 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/24/2012 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12150A367 (35) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 24, 2012 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260
Subject:
American Society of Mechanical Engineers, Section Xl Code, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-ISI-28
Reference:
Letter from the Tennessee Valley Authority to the Nuclear Regulatory Commission, "American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Owner's Activity Report for Cycle 16 Operation," dated July 6, 2011 In accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1995 Edition, 1996 Addenda as amended by 10 CFR 50.55a(b)(2)(xv)(A)(2), for one full penetration weld due to access limitations caused by design. This relief is requested for the Browns Ferry Nuclear Plant (BFN) Unit 2 Third Ten-Year Inspection Interval which began May 25, 2001 and ended May 24, 2011.
Specifically, this request for relief addresses one reactor pressure vessel nozzle-to-vessel (head) full penetration weld and nozzle inside radius section. Ultrasonic examinations were performed on the accessible areas of this weld to the maximum extent practical given the design configuration of the weld. The enclosure to this letter contains the BFN Unit 2, Request for Relief 2-ISI-28, for NRC review and approval.
Printed on recycled paper.
U.S. Nuclear Regulatory Commission Page 2 May 24, 2012 This request for relief is consistent with the BFN Unit 2 Request for Relief 2-ISI-6 and 2-ISI-13 submitted by TVA letter dated May 24, 2002. The NRC approved this request by letter dated April 3, 2003.
TVA requests approval of this request for relief within one year from the date of this letter.
There are no new regulatory commitments contained in this letter. If you have any questions, please contact Tom Hess at (423) 751-3487.
Resp c fully, Ma~ger, Corporate Nuclear Licensing
Enclosure:
Browns Ferry Nuclear Plant, Unit 2, American Society of Mechanical Engineers,Section XI Code Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 2-ISI-28 cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers,Section XI Code Inservice Inspection Program, Third Ten-Year Inspection Interval Request for Relief 2-ISI-28 (See Attached)
E-1
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers,Section XI Code Inservice Inspection Program, Third Ten-Year Inspection Interval Request for Relief 2-ISI-28 Executive Summary:
In accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for the N10 Reactor Pressure Vessel (RPV) nozzle-to-vessel full penetration weld and inside radius section ultrasonic (UT) examination performed during the Unit 2 Cycle 16 Refueling Outage in the Third period of the Third Ten-year interval.
The design configuration of the N10 RPV nozzle-to-vessel weld precludes a 100 percent UT examination of the required volume for the full penetration weld of the nozzle listed in the Table of this enclosure. This examination limitation occurs when the ASME Section XI, 2001 Edition, in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), examination requirements are applied in areas of components constructed and fabricated to early plant designs. Based on a construction permit date prior to January 1, 1971, BFN is exempt from meeting certain provisions of the ASME Code requirements for examination access, to the extent practical, within the limitations of design, geometry, and materials of construction of the components in accordance with 10 CFR 50.55a(g)(4).
A UT examination was performed on the accessible areas to the maximum extent practical given the physical limitations of the subject weld. The subject weld was examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, as required by 10 CFR 50.55a(g)(4), and 10 CFR 50.55a(g)(6)(ii)(C).
TVA concludes that performance of a UT examination of essentially 100 percent of the RPV nozzle-to-vessel full penetration weld and inside radius would be impractical. The performance of the UT examination of the subject weld and inside radius to the maximum extent practical provides an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld and nozzle. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii),
TVA requests that relief be granted for the BFN Unit 2 third Ten-Year inspection interval.
E-2
This relief is requested for the Browns Ferry Nuclear Plant (BFN) Unit 2 Third Ten-Year Inspection Interval which began May 25, 2001 and ended May 24, 2011.
Unit: Browns Ferry Nuclear Plant, Unit 2 System: Reactor Pressure Vessel (RPV), System 329 ASME Code Components Affected: One (1) RPV Nozzle-to-vessel full penetration weld and inside radius as listed in the Table of this enclosure.
ASME Code Class: ASME Code Class 1 (Equivalent)
Section Xl Edition: 1995 Edition, 1996 Addenda in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), by following the Electric Power Research Institute's (EPRI) Performance Demonstration Initiative (PDI) processes.
Code Table: IWB-2500-1 Code Examination Category: B-D, "Full Penetration Welds of Nozzles in Vessels" Code Examination Item Number: B3.90, "Reactor Vessel Nozzle-to-Vessel Welds" and B3.100, "Nozzle Inside Radius Section" Code Requirement: ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and B3.100 requires a volumetric examination of essentially 100 percent of the weld and adjacent base material and inside radius as depicted in Figure IWB-2500-7(a).
Code Requirements from Which Relief Is Requested: Relief is requested from the requirement of ASME Section Xl Code, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and B3.100 to perform essentially 100 percent volumetric examination of the weld and adjacent base material.
List of Components Associated with this Request for Relief: Nozzle-to-Vessel Weld N10-NV and N10-1R nozzle inside radius section.
Reason for Request: The approximately 2-inch Standby Liquid Control (SLC) nozzle is designed with an integral socket to which the boron injection piping is welded. The Standby Liquid Control nozzle is located in the bottom head of the reactor pressure vessel in an area that is inaccessible for examination from inside of the vessel. The design configuration of the RPV nozzle-to-vessel (N10-NV) weld area precludes a UT examination of essentially 100 percent of the required volume. The component design configuration limits UT examination coverage of the weld to the percentages listed in the Table of this enclosure.
Proposed Alternative and Basis for Use: In lieu of the ASME Code required essentially 100 percent volume UT examination, on the nozzle to vessel weld and inside radius section, TVA proposes a UT examination of accessible areas to the maximum extent practical given the component design configuration of the RPV nozzle-to-vessel weld.
E-3
Justification for Granting Relief: The design configuration of the subject nozzle-to-vessel weld (N10-NV), precludes UT examination of essentially 100 percent of the required examination volume. The inside radius section socket is welded to piping which injects boron. In order to examine the weld in accordance with the ASME Code requirements the RPV would require extensive design modifications. The physical arrangement of the nozzle-to-vessel weld precludes UT examination from the nozzle side. The limitations are inherent to the barrel-type nozzle-to-vessel weld design. The subject weld was examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, in accordance with the requirements of the 2001 Edition, in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), by following the Electric Power Research Institute's (EPRI) PDI processes.
Radiographic examination as an alternate volumetric examination method was determined to be impractical due to the radiological concerns and accessibility to the inside surface of the RPV to place radiographic film. The additional ASME Code coverage gained by radiography is impractical when weighed against the radiological concerns.
Therefore, TVA concludes that performing a UT examination of essentially 100 percent of the nozzle-to-vessel full penetration weld and inside radius section would be impractical.
Further, it would also be impractical to perform other volumetric examinations (i.e.,
radiography) which may increase examination coverage.
A maximum extent practical UT examination of the subject areas and a visual (VT-2) examination of the nozzle area performed each refueling outage in conjunction with the Class I System Leakage Test provides an acceptable level of quality and safety. TVA concludes that significant degradation, if present, would be detected during a UT examination performed to the maximum extent practical of the subject weld. The inside radius section socket is welded to piping which injects boron at locations removed from the nozzle thus eliminating any thermal stratification possibility at the nozzle inside radius section. A VT-2 examination of the nozzle area, performed at each refueling outage in conjunction with the Class 1 System Leakage Test will provide for detection of flaws when they are small and can be repaired prior to the SLC nozzle losing the ability to perform its intended function. As a result, reasonable assurance of operational readiness of the subject weld and inside radius section is provided.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN Unit 2 third Ten-Year ISI inspection interval.
Implementation Schedule:
This request for relief is applicable to the third Ten-Year ISI inspection interval for BFN Unit 2 which began May 25, 2001 and ended May 24, 2011. The weld and inside radius section described above is listed in the Table of this enclosure. The weld and inside radius section was examined during the third period (Cycle 16 - Spring 2011) of the third Ten-Year inspection interval.
E-4
Precedent:
This request for relief is consistent with BFN Unit 2 Request for Relief 2-1SI-6 and 2-ISI-13 submitted by TVA letters dated May 24, 2002 and February 14, 2003. The NRC approved these requests by letter dated April 3, 2003.
Attachments:
Sketch (Attachment A):
SK-B2202 Examination Reports (Attachment B):
Examination Report 2-TVA-N1O-NS Examination Report 2-'VA-N1O-IR E-5
Table Nominal Examination Weld Number /
Pipe Size ISI Drawing Coverage Unit / Cycle Comments (System)
(NPS)
Number Percent Inspection Performed Nozzle to vessel weld (SLC Nozzle)
N10-NV/
-2" SK-B2022 86.2%
2/16 examined using a 50 degree shear wave Standby Liquid mode and a 60 degree longitudinal wave mode. The examination was conducted Control (SLC)
(Spring 2011) from the vessel outside diameter surface.
Scanning was restricted due to nozzle configuration. This weld was examined using PDI qualified personnel, procedures, and equipment. The coverage claimed is 86.2%.
Nozzle to vessel weld (SLC Nozzle Inside N10-IR
--2" SK-B2022 90%
2/16 Radius) examined using a 65 and 70 (SLC) degree shear wave mode. The examination was conducted from the (Spring 2011) vessel outside diameter surface.
Scanning was restricted due to nozzle configuration. This weld was examined using PDI qualified personnel, procedures, and equipment. The coverage claimed is 90%.
E-6
Attachment A Inservice Inspection Drawing /Sketch Sketch SK - B2022 E-7
-j tlD z
In CD to w an K
'N m
C7 m
rP P3 33 C3 FIIAS5IBNM AB'Mo ASA (1 Cu
-n a1 NOTE: tHIs SKETCH IS FOR 151 PROGRAM USE ONLY AND I SK-82822 SHALLI NO] BE USED FOR FABRICATION/INSTALLATION.
II I
WELD DETAIL DIFFE~RENTIAL PRiESSUR~E IAOO-5306 I BROWNS FERRY 2 1 "
AND LIQUID CONTROL.
NOZZLE NIS I
i SK-82022
"" 00
Attachment B Weld Examination Reports Examination Report 2-TVA-N1O-NS Examination Report 2-TVA-N10-1R
000150
-ftaftO-196,LTO A
AREVA BROWNS FERRY NUCLEAR U2R16 REACTOR VESSEL NOZZLE AND CLOSURE HEAD ULTRASONIC EXAMINATIONS
- FINAL REPORT -
SECTION 10 N10 NOZZLE-TO-VESSEL WELD EXAMINATION DATA This section contains RV N10 Nozzle-To-Vessel Weld UT examination data.
Section 10 Page 149 of 182
Ve 000151 44tý Ultrasonic Examination Summary Report No.: 2-TVA-NtO-NS A
IComponentID:
Ne-NV AR EVA Nozzle to Vessel Welds Work Document:
2-Sl-4.6G Customer.
WVA Code Category:
B-D System:
RP`V (N10)
Site I Unit:
BFN 2 Code item:
B3.90 Material:
CS (Clad)
Outage: U2R16 Code Class:
I ISO I Drawing(s):
122858 E/ SK-B2022 Dewrlptlon:
Nozzle to Shell weld EPRI Model No.:
IR-2003-31 Procedure:
N-UT-78, Rev 0005 (with PDI-UT-6, Rev G).
Title:
PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Welds PDI-UT-6.
Procedure:
54-1S1-850, Rev 007.
Tide:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to
Title:
Shell Welds (inner 15%).,
Calibration Exam Data Coverage Coverage Indication Indication Sheets Sheets Work Sheets Diagrams Data Sheets Plot Shoots CS-01 EDS-01
- See Comments COS-01 NIA N/A CS-02 CDS-02 CS-03 I
I _
I Exam Resuit No Recordable Indications Exam Volume Coverage Obtained:
86.2%
Examiner: Edward P. Mazyck In accordance with UT Procedure N-UT-78, Rev 0005. with PDI-UT-6, Rev G. and EPRI Model No. IR-2003-31, a 60S axial and circumferential examination was performed from the vessel surface. The radial exam volume includes 100% of the component thickness and the 60" circumferential examination covers the outer 85% of the component thickness.
In accordance with UT Procedure 54-4SI-850-007 and EPRI Model No. IR-2003-31, a 50- Shear wave circumferential exam was performed from the vessel surface. This examination covers the inner 15% of the examination volume.
[~N118 Axial Scan Modein0 P araeer FrobeAngle I Mode Probe Skew Min R Max R Min MP Max MP 6Long.
0 2.84 15.38 0.14 12.03 N10 Clrcumferentlal Scan Modeling Parameters Probe Angle I Mode I Pfthe Skew Min R Max R Min MPI Max MP 50" Shear
- (13 to 40) 7.05 1 8.91 8.20 9.60 60" Long.
- (12 to 90) 2.83 _
10.26 0.14 1.0.32 This ultrasonic exeamination was perfomed in accordance with te criteria of 100FR 50.55a (b) (2) (xv) (0) and the minimum coverage requirements of t0CFR 50.55a (b) (2) (xv) (K) was achieved to the maximum extent possible.
This examination was performed using the alternative examination volume defined In Code Case N-613-1 which reduces the area to be examined per IWB-2500-7 (a) and (b) to the weld plus a W" on each side.
This examination satisfies the requirements of ASME Sec. XI 2001 Edition with 2003 Addenda for Appendix VIII, Category B-D, for item number B3.90. figure number PAVB 2500-7(a) exam volume, and was performed using ASME Sec XI, Appendix VIII qualified personnel, procedures, and equipment as amended by the Fmnal Rule.
Exam Coverage - 74.6% Circumferential coverage + 97.9% Axial coverage - 862% Total Coverage.
Personnel Nameum Signature Level Date Prepared By:
Edward P. Mazyck II 03-10-2011 I
~
AREVA Review: 1 Paul S. Anderson III 03-13-2011
____Customer.
AWIr14irWz 0,q~
ANagI10
! 5
(
Page 150 ot 182
000152
.j.
A RPV MANUAL ULTRASONIC AR EVA CALIBRATION DATA SHEET Component ID: N=0-NV Cal Shoo No.: CS-01 Repot No.: 2-TVA-N10 NS Customer Information Utility: TVA Site: Browns Ferry Unit 2 Procedure Infonmaton Procedure Number. 54-181-850 Rev.: 007 Procedure
Title:
Manual Ultrasonic Examination BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (Inner 15%)
UT.-hai~
mt Infoution Search Unit lnfbmalMn Reference I Cal. Block Info Manufacturer. Krautkramer Manufacturer: KBA Block Serial No.: BF-18 Model: USN 58Lsw Model: 892-600 Block Material: CS I Clad Serial Number: 01C3M3 Serial No.: 01TPCH Block Thickness: (*): 6.125 Range: 12.00 Nominal Angle (0): 50 Cal. Reflector Type: ID Notch Velocity (in/uSec): 0.1230 Measured Angle (0): 50 Cal. Reflector Size: ("): 0.250 Delay (uSec): 28.1028 Frequency (MHz): 2.25 Cal. Reflector Depth: ('): 0.253 Frequency (MHz): 2.25 Mode: Shear Miscelall eous Infomnatko Dual: [] On Off No. of Elements: I Cable Type: RG-174 Rectify: Fullwave Element Size: 0.5" X 1.0" Cable Length ('): 12 Pulse Width (ns): 220 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: N/A Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: Single Couplant Batch No.: 10325 B Puloer I Energy: Square Squint Angle (0): N/A Thernometer SIN: VH-11836 Voltage (V): 450 Wedge Radius: NIA Cal. Block Tamp (0 F): 76 Damping (a): 500 Wedge Skew: N/A Callbration I Verficato Infobmaton_
Calibration Responses Calibraton Time I Date Response (
9.42 MP []Depth J Gain (dB): 45.0 1Amp (%): 80 Initial Cal.: 0920 I 03-10-2011 Verification Responses Final Cal.: 1505 I 03-10-2011 Block No.: 6564 I Reflector(s): 2" & 5" Cal. Veriflcatho:1218 / 03-10-2011 Response (R): 2 O]MP []Depth Gain (dB): 20.8 Amp (%): 80 Cal. Verification: NIA Response (): 5 OMP [:]Depth IGain(dB): 20.8 Amp(%): 28 Cal. Verification: NIA Comments:
Exarnln-*r~dWard:P,,Msazyck,~ Level: 11 Examiner. N/A Level:
Sign:
I' Date: 03-10-2011 Sign-ae AREVA Meview Paul S, arson Sig Level: III Date: 03-13-2011 S* n
,°.-.....
Page 151 of 182
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A RPV MANUAL ULTRASONIC AR EVA CALIBRATION DATA SHEET Component ID: N10-NV TCal. Sheet No.: CS-02 Report No.: 2-TVA-N10 NS Cusomner InIbnnrain Utility: TVA Sift: Browns Ferry Unit-2 Procedure Informatlon Procedure Number. N-UT-78 I Rev.: 0005 Procedure
Title:
PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-6 UT lnstrumd Information Search Unit Information Reference I Cal. Block Info Manufacturer:. Krautkramer Manufacturer: RTD Block Serial No.: BF-18 Model: USN 58Lsw Model: TRl.2-Aust Block Material: CS I Clad Serial Number:. 01C3M3 Serial No.: 06-755 Block Thickness: ("): 6.125 Range: 6.0" Nominal Angle (0): 60 Cal. Reflector Type: %, T-SDH Velocity (in/uSec): 0.2300 Measured Angle (0): 61 Cal. Reflector Sie: ('): 5/16 SDH Deley (uSec): 15.6234 Frequency (MHz): 2.0 Cal. Reflector Depth: (*): 1.6 Frequency (MHz): 2 - 25 Mode: Longitudinal Mlacelmsllaeou Information Dual:
0 On []Off No. of Elements: 2 Cable Type: RG-174 Rectify: Fulkwave Element Size: 2(24 X 42)mm % a Cable Length ('): 12 Pulse Width (no): 250 Element Shape: Rectangle Intermediate Connentors: 0 Reject (%): 0 Focusing: FD - 2.70" Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: D-SBS Couplant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (0): 3*
Thermometer S/N: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Damping (0): 500 Wedge Skew: NWA Calibration I Verifiaton Infomiation Calibration Responses Calibration Time I Date Response (s): 3.152 E11MP Q-]Depth I Gain (dB): 47.8 Amp (%): 80 Initial Cal.: 0910 / 03-10-2011 Verification Responses Final Cal.: 1455 I 03-10-2011 Block No.: 6564 1 Reflector(s): 2-Radius Cal. Vedfilcation:1004/ 03-10-2011 Response ('): 2.1
(@MP Q"]Depth Gain (dB): 33.0 Amp (%): 80 Cal. Verification: N/A Response ():
N/A
[IMP []Depth Gain (dB): N/A Amp (%): NIA Cal. Verification: N/A Comments:
Zone I I Examiner: NIA Level:
Date:
in:
Date: 03-13-2011 Page 152 of 182
0F20O0c1.4 A
RPV MANUAL ULTRASONIC AR EVA CALIBRATION DATA SHEET Component ID: N10-NV Cal. Sheet No.: CS-03 Report No.: 2-TVA-N10 NS Custoerr Infomiatlon Utility,: TVA SM.e Browns Ferry Unit: 2 PmrocedurInom uto Procedure Number. N-UT-78 Rev- 0005 Procedure T111: PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-6 Iff 1009natp~ut IrbMfoimWo Search Un~tilbIfonatlon Rellrence I Cal. Block Info Manufacturer:. Krautkramer Manufacturer: RTD Block Serial No.: OF-18 Model: USN 58Lsw Model: TRL2-Aust Block Material: CS I Clad Serial Number: 01C3M3 Serial No.: 06-755 Block Thickness: ("): 6.125 Range: 18.0" Nominal Angle (0): 60 Cal. Reflector Type: ID Notch Velocity (in/uSec): 0.2300 Measured Angle (): 61 Cal. Reflector Size: ("): 0.250 Delay (uSec): 15.6234 Frequency (MHz): 2.0 Cal. Reflector Depth: ('): 0.253 Frequency (MHz): 2 - 25 Mode: Longitudinal MIMscelaneous Information Dual: N On [] Off No. of Elements: 2 Cable Type: RG-174 Rectify: Fulkwave Element Size: 2(24 X 42)rmm '% i Cable Length (): 12 Pulse Width (ns): 250 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: FD - 2.70" Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: D-SBS Couplant Batch No.: 10325 B Pulker! Energy: Square Squint Angle ():
3o Thermometer SIN: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Damping (a): 500 Wedge Skew: N/A Caliratn I Verifcation lnformatIon Calibration Responses Calibration Time I Date Response ('): 12.54 OQMP l]Depth IGain (dB): 58.6 Amp (%): 80 Initial Cal.: 0912 1 03-10-2011 Verification Responses Final Cal.: 1457 I 03-10-2011 Black No.: 6564 Refiecto(s): 2-Radius Cal. Verlflcatlon:1110 / 03-10-2011 Response (): 2.1 OMP []Depth Gain (dB): 33.0 Amp (%): 80 Cal. Verification: N/A Response ():
OMP []DepthI Gain (dB):
Amp (%):
Cal. Verification: N/A Comments:
Zone 2 Examine Edad.Mazyck 1
Lvel: II Examiner:
Level.,
Sin:
-Dt:03-10-2011 1Sign:
Date:
AREV Paul S Aderson sg:Level:
IIl Date: 03-13-2011 Sign:
Page 153 of 182
0 0
A UT EXAMINATION DATA SHEET Report No.: 2-TVA-NIO-NS AR EVA Nozzle to Shell Exam Data Sheet No.: EDS-01 mumcu n
w i
I InUm n
n erIno, aton,,
Co rn,limsnt lw on~w I f
,.Util:
A.Plant:
Browns Ferry Unit 2 Weld ID: N10 NV Pioedu@
I Model Infomwatio Exam Surface: Vessel O.D.
Proc. No.: 54-isn-850 Rev.: 007 Material: Carbon Steel (Clad)
Proc. No.: N-UT-78 I PDI-UT-6 Rev.: 0005 / G Configuration: Nozzle to Shell Table's I and 2: PDI-UT-6 Rev.: 15 System: RPV Modeling Report No.: (EPRI) IR-2003-31 Surface Condition: Smooth ExamInation Infomamon Lo Location: Nozzle Top Dead Center Wo Location: Nozzle Boss (RNozzle)
Exam Start Date: 03-10-2011
[Exam Start Time: 1005 Component Temp.: 96" Thennometer Serial No.: VH-11836 Exam End Date: 03-10-2011 Exam End Time: 1255 CoWWle
__Typo:
Utae III Complaint Batch No.: 10325 B Search Scan Surface Examination Cal Sheet Exam Recordable Unit Blend Nozzle Vessel Skew Angles No.
Sensitivity Indications Limitations Notes:
Radius Boss 500 Shear X
- (13 to 40)
CS-01 63.0 No CDS-02 60RL X
- (120 to 900) (0")
CS-02 65.8 No CDS-01 f 02 Zone-I 60' RL X
+/-(120 to 90°) (0°)
CS-03 68.6 No CDS-01 *0 2 Zone-2 Notes:
Scans performed as directed by EPRI Model Report No.: IR-2003 31.
Performed both axial and circumferential weld examinations using 60°RL.
Exmn**w~
- Mayk/Examiner:
N/A Lo I:
ae Sain:
Ma4z Level: II Date: 03-10-2011 in:Level:
Date.
AKV v
- 1*
P l
n Level:
Date: 03-13-2011
- Il 00 0
C,'
0 01 CD.
A EA UT Coverage Data Sheet Report No.: 2-rvAN1O-NS AR EVA Coverage Data Sheet No.: CDS-01 Cuebomw Infom on
- ,n Comn~hnt inforiationl Utility: TVA Plant: Browns Ferry Unit: 2 Weld 10: N10-W TConfiguration: Nozzle to Shell Axial Examination Coverage i
t~4.2" Area of Limitation = 0.4 in'2 Axiul Examination Coverage Total examination Area = 18.80 in2 Area of Circ. Limitation = 0.4 In2
% of Area Examined =
I Total Area Inspected I Total Area=
Total Examination Coverage =
18.40 In! 18.80 in 2 = 87.9%
%.I 0.
0 I
Report No.: 2-1VA-N10-NS UT Coverage Data Sheet Coverage Data Sheet No.: CDS-02
.Customer Information
.1 Component Information Utility: TVA Plant: Browns Ferry Unit: 2 Weld ID: N-NV.
Configuration: Nozzle to Shell Circumferential Examination Coverage Area not Interogated 0.A4 In2 -
Area Interogated n 6.03 In2 2 No Coverage Credit Upper 85% TL 60* Coverage Obtained :9.54 In 2 i,
Upper 85% Cire. Exam Coverage I
Total examination Area 1 16.01 in" I
Area Covered = 9.54 in" Total Examination Coverage = 59.6%
Lower 15% Circ. Exam Coverage
- \\I Total examination Area = 2.79 in'
".?
Total Examination Coverage =100%
Vtighted average 100% x 15% = 15%
"\\*.
ZI Composite Circumferential Coverage I
59.6% + 15% = 74.6% Total Circ. Coverage I
Lower 15%T I
Area Coverage Obtained m 2.79 In2 2 Total Inspection Area 18.80 IN2 Ru SI
000158 VE -/)- 01q Ultrasonic Examination Summary Report No.:
2-1VA-N1O-NS A
Component ID:
N1I-NV R EVA Nozzle to Vessel Welds IWork Document:
2-SI-4.6G I
I I
q Customer:
TVA I Code Category: I B-D System: I RPV (N10)
Site I Unit:
BFN 2 Code Item:
B3.90 Material:
CS (Clad)
Outage:
U2R16 Code Class:
I ISO I Drawing(s):
122858 E I SK-B2022
==
Description:==
Nozzle to Shell weld EPRI Model No.:
IR-2003-31 Procedure:
N-UT-78, Rev 0005 (with PDI-UT-6, Rev G).
Title:
PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Welds PDI-UT-6.
Procedure:
54-ISI-850, Rev 007.
Title:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (inner 15%).
Calibration Exam Data Coverage Coverage Indication Indication Sheets Sheets Work Sheets Diagrams Data Sheets Plot Sheets CS-01 EDS-01
- See Comments CDS-01 N/A N/A CS-02 ICDS-02 CS-03
___,Neralnitos__lu 1
__,__._86.2%
76 No Recordable Indications or Vi.Cvrage band 62 Examiner: Edward P. Mazyck In accordance with UT Procedure N-UT-78, Rev 0005, with PDI-UT-6, Rev G, and EPRI Model No. IR-2003-31, a 600 axial and circumferential examination was performed from the vessel surface. The radial exam volume includes 100% of the component iCkness and the 80 circumferential examination covers the outer 85% of the component thickness.
accordance with UT Procedure 54-ISI-850-007 and EPRI Model No. IR-2003-31, a 500 Shear wave circumferential exam was from the vessel surface. This examination covers the inner 15% of the examination volume.
L*-*
~
- t9
- .A,0" ibI Scan ModeI i
mers Probe An.le I Mod Probe Skew Min R Max R Mi MP Max MP 60"Long.
0 2.84 15.38 0.14 12.03 Prb.
.Ni.
Clrcumfe 9I8l 01 ModelIng POO.mstem Probe Angie I Mode Probe Skew Min R Max R Min M
P Max MP 50' Shear
+/-(13 to 40) 7.05 8.91 8.20 9.60 600 Long.
+/-(12 to 90) 2.83 10.26 0.14 10.32 This ultrasonic examination was performed in accordance with the criteria of 10CFR 50.55a (b) (2) (xv) (G) and the minimum coverage requirements of IOCFR 50.55a (b) (2) (xv) (K) was achieved to the maximum extent possible.
This examination was performed using the alternative examination volume defined in Code Case N-613-1 which reduces the area to be examined per IWB-2500-7 (a) and (b) to the weld plus a 'A' on each side.
This examination satisfies the requirements of ASME Sec. XA 2001 Edition with 2003 Addenda for Appendix VIII, Category B-D, for item number B3.90, figure number IWB 2500-7(a) exam volume, and was performed using ASME Sec XI, Appendix VIII qualified personnel, procedures, and equipment as amended by the Final Rule.
Exam Coverage = 74.6% Circumferential coverage + 97.9% Axial coverage = 86.2% Total Coverage.
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Signature Level Date i"1
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Prepared By:
Edward P. Mazyck II 103-10-2011
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AREVA Review:
Paul S. Anderson III 03-13-2011 Customer: JA~r~~
ANII: j 42#fte~d 40____1
000159 V6--I1- ) 7 A
AREVA RPV MANUAL ULTRASONIC CALIBRATION DATA SHEET Component ID: N 10-NV I Cal. Sheet No.: CS-01 I Report No.: 2-TVA-N10 NS Utility: TVA Site: Browns Ferry I Unit: 2 7 I Procedure Number: 54-1SI-850 I Rev.: 007 Procedure
Title:
Manual Ultrasonic Examination BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (inner 15%)
Manufacturer: Krautkramer Manufacturer: KBA Block Serial No.: BF-18 Model: USN 58Lsw Model: 892-600 Block Material: CS / Clad Serial Number: 01C3M3 Serial No.: 01TPCH Block Thickness: ("): 6.125 Range: 12.0" Nominal Angle (0): 50 Cal. Reflector Type: ID Notch Velocity (inluSec): 0.1230 Measured Angle (0): 50 Cal. Reflector Size: ("): 0.250 Delay (uSec): 28.1028 Frequency (MHz): 2.25 Cal. Reflector Depth: ("): 0.253 Frequency (MHz): 2.25 Mode: Shear Dual: [] On 0 Off No. of Elements: I Cable Type: RG-174 Rectify: Fullwave Element Size: 0.5" X 1.0" Cable Length ('): 12 Pulse Width (ns): 220 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: N/A Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: Single Couplant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (0): N/A Thermometer S/N: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Calibration Responses Calibration Time I Date Response ("): 9.42 ZMP []Depth Gain (dB): 45.0 Amp (%): 80 Initial Cal.: 0920 I 03-10-2011 Verification Responses Final Cal.: 1505 I 03-10-2011 Block No.: 6564 Reflector(s): 2" & 5" Cal. Verificadon:1218 / 03-10-2011 Response ("): 2 OMP []Depth Gain (dB): 20.8 Amp (%): 80 Cal. Verification: N/A Response ("): 5 NMP []Depth Gain (dB): 20.8 Amp (%): 28 Cal. Verification: N/A Comments:
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Examiner: -uwaro.
MazyG/"
LV.I; ii axaminer: rN/A Sign:
10,*.
-I,.ii, Date: 03-10-2011 1 Sign:
Level:
Date:
SAREVA Review: Paul S A deron L
Sign:
Level: III Date: 03-13-2011
000160 I
A AREVA RPV MANUAL ULTRASONIC CALIBRATION DATA SHEET I Cal. Sheet No.: CS-02 I Report No.: 2-TVA-N10 NS I'
Utility: TVA Site: Browns Ferry Unit:2 Procedure Number: N-UT-78 Rev.: 0005 Procedure
Title:
PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-6 Manufacturer. Krautkramer Manufacturer: RTD IBlock Serial No.: BF-1 8 Model: USN 58Lsw Model: TRL2-Aust Block Material: CS / Clad Serial Number: 01C3M3 Serial No.: 06-755 Block Thickness: ("): 6.125 Range: 6.0" Nominal Angle (s): 60 Cal. Reflector Type: % T-SDH Velocity (in/uSec): 0.2300 Measured Angle (0): 61 Cal. Reflector Size: ("): 5/16 SDH Delay (uSec): 15.6234 Frequency (MHz): 2.0 Cal. Reflector Depth: ("): 1.5 Frequency (MHz): 2 -25 Mode: Longitudinal__.______
Dual: 0 On [I Off No. of Elements: 2 Cable Type: RG-174 Rectify: Fullwave Element Size: 2(24 X 42)mm %,
Cable Length ('): 12 mm t
Pulse Width (ns): 250 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: FD - 2.70" Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: D-SBS Couplant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (0): 3*
Thermometer SIN: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (o F): 76 Damping (a): 500 Wedge Skew: N/A Calibration Responses Calibration Time I Date Response ("): 3.152 IZMP []Depth Gain (dB): 47.8 Amp (%): 80 Initial Cal.: 0910 / 03-10-2011 Verification Responses Final Cal.: 1455 / 03-10-2011 Block No.: 6564 Reflector(s): 2" Radius Cal. Verlflcation:1004 / 03-10-2011 Response("): 2.1 ZIMP [-Depth Gain (dB): 33.0 Amp(%): 80 Cal. Verification: N/A Response ("): N/A
[IMP ElDepth Gain (dB): N/A Amp (%): N/A Cal. Verification: N/A Comments:
Zone 1 Examiner: ri1 Sign:
Level:
Date:
Date: 03-13-2011
000161
~i41-0191 U,
A AREVA RPV MANUAL ULTRASONIC CALIBRATION DATA SHEET Component ID: N10-NV I Cal. Sheet No.: CS-03 I Report No.: 2-TVA-N10 NS Procedure Number: N-UT-78 Rv:00 Procedure
Title:
PDI Generic Procedure for the Manual Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-6 I
a 1:7174- ý,
0 Manufacturer~ Krautkramer Manufacturer. RTD Block Serial No.: BF-1 8 Model: USN 58Lsw Model: TRL2-Aust Block Material: CS I Clad Serial Number: 01C3M3 Serial No.: 06-755 Block Thickness: ("): 6.125 Range: 18.0" Nominal Angle (0): 60 Cal. Reflector Type: ID Notch Velocity (in/uSec): 0.2300 Measured Angle (0): 61 Cal. Reflector Size: ("): 0.250 Delay (uSec): 15.6234 Frequency (MHz): 2.0 Cal. Reflector Depth: ("): 0.253 Frequency (MHz): 2 -25 Mode: Longitudinal Dual: 0 On [- Off No. of Elements: 2 Cable Type: RG-174 Rectify: Fullwave Element Size: 2(24 X 42)mm a
- Cable Length ('): 12 Pulse Width (ns): 250 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: FD ~2.70" Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: D-SBS Couplant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (a): 30 Thermometer SIN: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Dmig(0l): 500 Wedge Skew: N/A Calibration Responses Calibration Time I Date Response (m): 12.54 IZMP [:]Depth Gain (dB): 58.6 Amp (%): 80 Initial Cal.: 0912 I 03-10-2011 Verification Responses Final Cal.: 1457 I 03-10-2011 Block No.: 6564 Reflector(s): 2" Radius Cal. Verification:1 110 / 03-10-2011 Response ("): 2.1 0MP EJDepth Gain (dB): 33.0 Amp (%): 80 Cal. Verification: N/A Response ("):
I-MP []Depth Gain (dB):
Amp (%):
Cal. Verification: N/A Comments:
Zone 2 Examiner-dward P.,Mazyck L Level: B1 Examiner:
Level:
Sin:
ate: 03-10-2011 Sign:
Date:
AREVA Rvie~w Paul S A rderso~n
,,,,-0,,,*
Paul SLevel:
Ill Date: 03-13-2011 Sign:
A U
T E X A M I N A T I O N D A T A S H E E T AREVA Nozzle to Shell Exam Data Sheet No.: EDS-01 Utility: TVA Plant: Browns Ferry Unit: 2 Weld ID: N10 NV Exam Surface: Vessel O.D.
Proc. No.: 54-ISI-850 Rev.: 007 Material: Carbon Steel (Clad)
Proc. No.: N-UT-78 / PDI-UT-6 Rev.: 0005 I G Configuration: Nozzle to Shell Table's I and 2: PDI-UT-6 Rev.: 15 System: RPV Modeling Report No.: (EPRI) IR-2003-31 Surface Condition: Smooth L0 Location: Nozzle Top Dead Center W0 Location: Nozzle Boss (RNozzle)
Exam Start Date: 03-10-2011 Exam Start Time: 1005 Component Temp.: 96 ThermometerSerial No.: VH-11836 Exam End Date: 03-10-2011 Exam End Time: 1255 Couplant Type: Ultragel II Couplant Batch No.: 10325 B Search Scan Surface Examination Cal Sheet Exam Recordable Unit Radius Nozzle Vessel Skew Angles No.
Sensitivity Indications Radiu Boss 500 Shear X
+/-(130 to 400)
CS-01 63.0 No CDS-02 600 RL X
+/-(120 to 900) (00)
CS-02 65.8 No CDS-01 / 02 Zone-1 600 RL X
+/-(120 to 900) (00)
CS-03 68.6 No CDS-01 /02 Zone-2 Notes:
Scans performed as directed by EPRI Model Report No.: IR-2003 31.
Performed both axial and circumferential weld examinations using 60°RL.
Examiner cwa P Mazyck Level: I Date: 03-10-2011 Examiner: N/A Level:
Date:
sign:
-Sign:
AR@=3A
-V *.'P uI
/KMnddrson Level:
Date: 03-13-2011 Sign:.0 1
CD C)
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A AREVA Report No.: 2-1VA-NiO-NS UT Coverage Data Sheet Coverage Data Sheet No.: CDS-01
,e II I
Customer Infonmldlon Component Information UtiIty: TVA Plant: Browns FerTy Unit: 2 Weld ID: N0-NV Configuration: Nozzle to Shell Axial Examination Coverage Area of Limitation O
GA in2
'I Ttlexamination Area =18.80 in2 Area of Circ, Umnitalon -0.4 iW 2
I
%ofAreaExamined I
Total Area Inspected I Total Area Total Examination Coverage =
18.40 in2i 18.80 in2 = 97.9%
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A AREVA Report No.: 2-rVA-N10-NS UT Coverage Data Sheet Coverage Data Sheet No.: CDS-02 Customer Infomislon.
Component Information Utility:
A Plant Browns Ferry Unit: 2 Weld ID: N0-NV Configuration: Nozzl to Shell Circumferential Examination Coverage Area not Interogated = 0.44 In2 I
Area Interogated = 6.03 In2 I
No Coverage Credit I
Upper 85% TI 606 Coverage Obtained a 9.54 In2 Upper 85% Cire. Exam Coverage
\\
i Total examination Area = 16.01 inI k
Area Covered = 9.54 ins
\\2 Total Examination Coverage = 59.6%
Lower 15% Cire. Exam Coverage Total examination Area = 2.79 int Total Examination Coverage =100%
,44 Weighted average 100% x 15% = 15%
Composite Circumferential Coverage 59.6% + 15% = 74.6% Total Circ. Coverage Lower 15% T Area Coverage Obtained " 2.79 In' 2*
I Total Inspection Area = 18.80 IN2 C)
A AR EVA cV-o 0 0001o BROWNS FERRY NUCLEAR U2RI 6 REACTOR VESSEL NOZZLE AND CLOSURE HEAD ULTRASONIC EXAMINATIONS
- FINAL REPORT -
SECTION 11 N10 NOZZLE INNER RADIUS REGION EXAMINATION DATA This section contains RV N10 Inner Radius Region UT examination data.
Section 11 Page 157 of 182
VG-f-ca-o 000166 V
Ultrasonic Examination Summary Report No.:
2-rVA-NI1-IR A
Component ID:
N10-1R A
EVA Inner Radius Work Document: 2-SI-4.8G Customer. TVA Gode Category:
B-D System: RPV (NI1)
Site I Unit:
BFN 2 Code Item; B3.100 Material:
CS (Clad)
Outage:
U2R16 Code Class: I Dr nISO/
122858 E / SK-B2022
==
Description:==
Nozzle Inside Radius Section EPRI Model No.:
IR-2004-43 Procedure:
544-81-850, Rev 007
Title:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (inner 15%).
Calibration Exam Data Coverage Coverage Indication Indication Sheets Sheets Work Sheets Diagrams Data Sheets Plot Sheets CS-01 EDS-01 See Note I N/A N/A N/A CS-02 Exam Resufte:
No Recordable Indications Exam Volume Coverage Oballned: 190%
In accordance with UT Procedure 54-1SI-850-007 and EPRI Model No. IR-2004-43, a 855 and 70* Shear wave Inner Radius examinations were performed from the vessel O.D. surface.
NIO Cirumeental Sen d
Parametewe Probe Angle I Mode I Probe Skew Min R Max R Min MP Max MP 655 ) Shear
- (I to 10) 13.85" 15.54' 14.14" 18.07w 70' / Shear
+(2 to 23) 2.94-15.54' 2.30" 16.07" (1) Reference EPRI Report IR-2004-43 for exam volume and coverage.
This examination satisfies the requirements of ASME Sec. X1 2001 Edition with 2003 Addenda for Appendix VIII, Category B-1, for item number B3.100, figure number IWB 2500-7(a) exam volume, and was performed using ASME Sec XI, Appendix VIII qualified personnel, procedures, and equipment as amended by the Final Rule.
Personnel Name (Signature Level Daft Prepared By: Edward P. Mazyclc
[1 103-10-2011 AREVA Review: I Paul S. Anderson III 03-13-2011 ini.
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-ii 11 Page 158 of 182
VjFij/ -0L9-O 00010"7 A
RPV MANUAL ULTRASONIC A R E VA CALIBRATION DATA SHEET Component ID: N10-4R Cal. Sheet No.: CS-01 Repout No.: 2-TVA-NI04-R Customer Information UUI-y: TVA Site: Browns Ferry Unit 2 Procedure Information Procedure Number: 54-lSI-850 Rev.: 007 Procedure
Title:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (inner 15%1 UT Instrument Information Search Unit Information Reference I Cal. Block Info Manufacturer. Krautkramer Manufacturer. KBA Block Serial No.: BF-18 Model: USN 58Lew Model: 892-00 Block Matsral: CS I Clad Serial Number. 01C3M3 Serial No.: O1TPCJ Block Thickness: ('): 6.125 Range: 18.0' Nominal Angle(): 65 Cal. Reflector Type: ID Notch Velocity (in/uSec): 0.1230 Measured Angle (0): 65 Cal. Reflector Sze: ('): 0.250 Delay (uSec): 14.7300 Frequency (MHz): 2.25 Cal. Reflector Depth: (): 0.253 Frequency (MHz): 2.25 Mode: Shear Miscellaneous Information Dual:
0 On 0 Off No. of Elements: I Cable Type: RG-174 Rtecify: Fuliwave Element Sime: 0.5' X 1.0 Cable Length r): 12 Pulse Widh (ne): 220 Element Shape: Rectangle Intennedlate Connectors: 0 Reject (%): 0 Focusng: N/A Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: Single Couplant Batch No.: 10325 B Pular I Energy: Square Squint Angle (0): N/A e SIN: VH-1 1836 Vo e M: 450 Wedge Radius: NIA Cal Block Temp (6 F): 76 Danipin (0): S00 Wiedge Skew:. NIA Callbatlon I Verification Information Calibration Responses Calibration Time I Date Response (): 13.77 0MP []Depth Gain (dB): 53.0 Amp (%): 80 Initial Cal.: 0930/ 03-10-2011 Verification Responses Final Cal.: 1508 1 03-10-2011 Block No.: 6664 Reflector(s): 2- & 5V CaL Verlflcation:1256 103-10-2011 Response ('): 2" JIMP []Depth Gain (dB): 18.8 Amp (%): 80 Cal. Verification: N/A Response (0): 5W
Min. MP = 14.147 Max MP = 16.0r Examiner-Edward P. Mazyck Level: II Examiner. N/A Level:
Sign:
D*.!-
Date: 03-10-2011 Sign:
Date:
AREVA Review: Dan Langenfetd L Sign:
A6444 Level: Ill Date: 03-13-2011 Page 159 of 182
y E-ooo 00100 A
RPV MANUAL ULTRASONIC AR EVA CALIBRATION DATA SHEET CornporintD: N1041R Cal. Sheat No.- CS.02 TiipRq tNo-- 2-TVA-N10-4R Customer Information Utl1ty: TVA Site: Browns FerTy UnIt: 2 Procedure Infomugai Procedure Number: 64481-850 Row.: 007 Procedure
Title:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (Inner 15%)
UT Inetumwent Information Search Unit Infolnation Reference I Cal. Block Info Manufacturer: Kraubtramer Manufacturer: KBA Block Serial No.: BF-1 8 Model: USN 58Lsw Model: 892400 Block Maltrial: CS / Clad Serial Number: 01C3M3 Serial No.: 01C4NX Block Thickness: (*): 5.125 Rane: 18.(r Nomia Angle (0): 70 Cal. Refector Type: % T-SDH Velocity (inluSec): 0.1230 Measured Angle (0): 70 Cal. Reflector Size: ('): 5116 DIX Delay (uSec): 14.0400 Frequency (MHz): 2.25 Cal. Relector Depth: ('): 4.375 Frequency (MHz): 2.25 Mode: Shear MIwellaneous Inrfomatlion Dual: 0] On N Off No. of Elements: I CableType: RG-174 Rectljf Fuiwave Element Sie: 0.5' X 1.0 Cable Length ('): 12 Pule* Width (no): 220 Element Shape: Rectangle Intrmed-ate Connectors: 0 Reject (%): 0 Focusing: N/A Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration; Single Couplant Batch No.: 10325 B Pulb I Energy: Square Squint Angle (0): N/A ennomterm SIN: VH-11836 Voltage (V): 450 Wedge Radlus: N/A CaL Block Temp (0 F): 76 Damping (0): 500 Wedge Skew:. N/A Calibration I Vedfication Information Calilbnion Responses Callibvatio Titus I Date Resonsem(0); 12.79 S]MP [1-)"th Gain (0l): 54.4 Amp()
80 hinitlCal.: OM25/ 03-10-2011 Verclo Responses Final Cal.: 15081/ 03-10-2011 Black No.: 6564 1Reflhc.tords): 2" & 5" Cal. Verfco:1 3361/03-10-2011 Response ("): 2" 0MP [-Depth Gain (dB): 25.5 Amp (%): 80 Cal. Veificallon: N/A Respons. C): 5U OMP O]DephI Gain (dB): 25.5 Amp (%): 40 Cal. Veillicalion: N/A Comments:
Min. MP = 2.30" Max MP = 16.07" Examiner: Edward P. Mazyck Level: 11 Examiner: NIA Level:
Sign:
Date: 03-10-2011 Sign:
Date:
AREVA Review: Dan Langenfeld Sign:
II
,,elO 03-13-2011 Page 160 of 182
O 0
A UT EXAMINATION DATA SHEET R"ort No.: 2-TVA-NI04R VNoainl Inr Radie Exam Date Sheet No.: EDS-01 Customer Information Comrn ent Information Utit "TVA I Plant: Browns Ferry Unit:2 Wed ID: N10 IR Systan: RPV Procedure I Model Informaion Exam Sf ace: Vessel O.0.
Surface Condition: Smooth Proc. No.: 54-.Sl-850 Rev.: 007 Mateiall: Carbon Steel (Clad)
Modanl Regp No.: (EPRI) IR-2004-43 Conflauration: Inner Radius Examination Information Le Location: Nozzle Top Dead Center W0Location: Nozzle Boss (RNozzle)
Exam Start Date: 03-10-2011 Exam Start Time: 1258 Component Temp.: 960 Thermome* Seal No.: VH-1 183 Exam End Data: 03-10-2011 Exam End Time: 1430 CCU Type: U txamel I I
CoupL3t Batch No.: 103256 Search Stan Surface Examination Exam Recordable Unit Blend Nozzle veinsel Skw Angles Cal Sheet No.
Sn IndicaonsNotes:
Radius Boss amkw gl eNsIi o
W5 Shear X
W(1 to 10)0 CS-01 65.0 No None.-
700 Shear X
k(2 to 23)0 CS-02 66.4 No None r_,
Notes: Scans performed as directed by EPRI Model Report No.: IR-2004 43.
SummaY of Deh n Modelin Parameters - IR-2004-43 Metal Pah IBeam angle at flaw I Mamum d
Min I Max I Min I Max I Migolent*non Angle e
2.30 16.07 40 90 18" 9
Examiner: Edward P. M,/uzyd*
Examnlna: N/A Sin:
.Edward P.
Level: II Dat: 03-10-201 I1 ne Level:
Date:
AREVA Review: Dan LangenferdL
- 0 Sign:
Level:ill Date: 03-13-2011
- 0 0
0 00 CZ)
C>
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to*
000170 VE-Ii-rjX0 r A Ultrasonic Examination Summary AREVA Inner Radius Report No.:
2-TVA-N10-1R Component 1D:
NI 2--IR Work Document:
2-SI-4.6G Customer: 4TVA Code Category:* B-D ISystem:
RPV (N10)
Site I Unit:
BFN 2 Code Item: j B3.100 Material:
CS (Clad)
Outage:
U2R16 Code Class:
I D
IS 122858 E / SK-B2022 I
I Drawing(s):
==
Description:==
Nozzle Inside Radius Section EPRI Model No.:
IR-2004-43 Procedure:
54-1SI-850, Rev 007 Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (ine 15%).
Calibration Exam Data Coverage Coverage Indication Indication Sheets Sheets Work Sheets Diagrams Data Sheets Plot Sheets CS-01 EDS-01 See Note I N/A N/A N/A CS-02 SNo Recordable Indications Exam Volume Cors. Obtained:. 190%
in accordance with UT Procedure 54-1SI-850-007 and EPRI Model No. IR-2004-43, a 65° and 70" Shear wave Inner Radius examinations were performed from the vessel O.D. surface.
0 7T.:y*10114551".
snew rodqaImVera...ters:"
Probe Angle / Mode Probe Skew Min R T Max R Min MP Max MP 650 I Shear
+/-(1 to 10) 13.85" 15.54" 14.14" 16.07" 700 / Shear
+/-(2 to 23) 2.94" 15.54" 2.30" 16.07" (1) Reference EPRI Report IR-2004-43 for exam volume and coverage.
This examination satisfies the requirements of ASME Sec. XI 2001 Edition with 2003 Addenda for Appendix VIII, Category B-D, for item number B3.100, figure number IWB 2500-7(a) exam volume, and was performed using ASME Sec XI, Appendix VIII qualified personnel, procedures, and equipment as amended by the Final Rule.
Perso.~I j
~Name Prepared By:
VA Review:
Customer:
I ANII:
F
000171 VE-1 LAO 1
I A
ARE VA RPV MANUAL ULTRASONIC CALIBRATION DATA SHEET Component ID: N10.IR I Cal. Sheet No.: CS-01 I Report No.: 2-TVA-N10-IR Customer Information Uility: TVA SRt: Browns Ferry Unit: 2 Procedure Infonmation Procedure Number: 54-1SI-850 Rev.: 007 Procedure
Title:
Manual Ultrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (Inner 15%)
UT Instrument Information Search Unit Information Reference I Cal. Block Info Manufacturer: Krautkramer Manufacturer: KBA Block Serial No.: BF-18 Model: USN 58Lsw Model: 892-600 Block Material: CS I Clad Serial Number. 01C3M3 Serial No.: 01TPCJ Block Thickness: ("): 6.125 Range: 18.0" Nominal Angle (0): 65 Cal. Reflector Type: ID Notch Velocity (in/uSec): 0.1230 Measured Angle (0): 65 Cal. Reflector Size: ("): 0.250 Delay (uSec): 14.7300 Frequency (MHz): 2.25 Cal. Reflector Depth: ("): 0.253 Frequency (MHz): 2.25 Mode: Shear Miscellaneous Information Dual: 0 On (@ Off No. of Elements: 1 Cable Type: RG-174 Rectify: FulIwave Element Size: 0.5' X 1.0" Cable Length ('): 12 Width (ns): 220 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: N/A Couplant Type: Ultragel 11 PRF I PRR Mode: AutoHigh Search Unit Configuration: Single Coupiant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (0): N/A Thermometer S/N: VH-11836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Damping (01): 500 Wedge Skew: N/A Calibration I Verification Information Calibration Responses Calibration Time I Date Response (0): 13.77 0MP [-Depth I Gain (dB): 53.0 lAmp(%): 80 Initial Cal.: 0930 / 03-10-2011 Verification Responses Final Cal.: 1508 I 03-10-2011 Block No.: 6564 Reflector(s): 2" & 5" Col. Veriflcatlon:1256 / 03-10-2011 Response ("): *21" IMP o[]Dpth Gain (dB): 18.8 Amp (%): 80 Cal. Verification: N/A Response (*): 5' 0MP
-Depth Gain (dB): 18.8 Amp(%): 28 Cal. Verification: N/A Comments:
Min. MP= 14.14" Max MP = 16.07" E Examiner. Edward P. Mazyck Level: II Examiner. N/A Level:
Sign:
Date: 03-10-2011 Sign:
Date:
AREVA Review: Dan Langenfeld Level: III Date: 03-13-2011 Sign:At
000172 V6-f-1-O r
I I
I A
AREVA RPV MANUAL ULTRASONIC CALIBRATION DATA SHEET Component ID: NIO-IR Cal. Sheet No.: CS-02 I Report No.: 2-TVA-NIO-IR Customer Information Utility: TVA Site: Browns Ferry Unit: 2 Procedure Information Procedure Number: 54-11-850 Rev.: 007 Procedure
Title:
Manual Vltrasonic Examination of BWR Reactor Vessel Nozzle Inner Radius Regions and Nozzle to Shell Welds (Inner 15%)
UTInstrumentinformation Search Unit Information Reference I Cal. Block Info Manufacturer: Krautkramer Manufacturer: KBA Block Serial No.: BF-18 Model: USN 58Lsw Model: 892-600 Block Material: CS / Clad Serial Number. 01C3M3 Serial No.: 01C4NX Block Thickness: ("): 6.125 Range: 18.0 Nominal Angle (0): 70 Cal. Reflector Type: Y T-SDH Velocity (in/uSec): 0.1230 Measured Angle (0): 70 Cal. Reflector Size: ("): 5/16 DIA.
Delay (uSec): 14.0400 Frequency (MHz): 2.25 Cal. Reflector Depth: ("): 4.375 Frequency (MHz): 2.25 Mode: Shear Miscellaneous Informatlon Dual: 0 On 0 Off No. of Elements: 1 Cable Type: RG-1 74 1j Rectify: Fullwave Element Size: 0.5" X 1.0" Cable Length ('): 12 m
1 t
Pulse Width (ns): 220 Element Shape: Rectangle Intermediate Connectors: 0 Reject (%): 0 Focusing: N/A Couplant Type: Ultragel II PRF I PRR Mode: AutoHigh Search Unit Configuration: Single Couplant Batch No.: 10325 B Pulser I Energy: Square Squint Angle (*): N/A Thermometer SIN: VH-1 1836 Voltage (V): 450 Wedge Radius: N/A Cal. Block Temp (0 F): 76 Damping (0): 500 Wedge Skew: N/A Calibraton I Verification Informaton_
Calibration Responses Calibration Time I Date Response ("): 12.79
[9MP [JDepth Gain (dB): 54.4 Amp (%): 80 Initial Cal.: 0925 / 03-10-2011 Verification Responses Final Cal.: 15081 03-10-2011 Block No.: 6564 Reflector(e): 2- & 5-Cal. VerIfication:1336 / 03-10-2011 Response (): 2' OMP []Depth Gain (dB): 26.5 Amp (%): 80 Cal. Verification: N/A Response (): 5' OMP [JDepth Gain (dB): 25.5 Amp (%): 40 Cal. Verification: N/A Comments:
Min. MP = 2.30" Max MP = 16.07" Examiner: Edward P. Mazyck Level: II Examiner: N/A Level:
SIgn:
n Date: 03-10-2011 Sign:
Date:
AREVA Review: Dan Langenfeld Level: III Date: 03-13-2011 Sign; zt*
6'
A AREVA Report No.: 2-TVA-N10-IR UT EXAMINATION DATA SHEET Nozzle Inner Radius Exam Data Sheet No.: EDS-0t Customer Information Component Information Utility: TVA Plant: Browns Fe Unit: 2 Weld ID: N10 IR I System: RPV Procedure I Model Infonnation Exam Surface: Vessel OD.
Surface Condition: Smooth Proc. No.: 54-1SI-850 I Rev.: 007 Material: Carbon Steel (Clad)
Modeling Report No.: (EPRI) IR-2004-43 Configuration: Inner Radius Examinaion Information L Location: Nozzle Top Dead Center Wo Location: Nozzle Boss (RNozzle)
Exam Start Date: 03-10-2011 Exam Start Time: 1258 ComponentTemp.: 96, ThermometerSerlal No.: VH-11836 Exam End Date: 03-10-2011 Exam End Time: 1430 Couplat Type: Ulre III Couplant Batch No.: 10325 B Search Scan Surface Examination Exam Recordable Unit Blend Nozzle Vessel Skew Angles Cal Sheet No.
Sensitivity Indications Limitations Notes:
Radius Boss 65* Shear X
+/-(1 to 10)I CS-01 65.0 No None 700 Shear X
+/-(2 to 23)0 CS-02 66.4 No None Notes: Scans performed as directed by EPRI Model Report No.: IR-2004 43.
Summary of Detection Modelin Parameters - IR-2004-43 Metl Path Beam angle at flaw I Maximum
% Coverage J Min I Max IMin IMax IMisorie,.a.ion Angle 2.30 16.07 40 90 180 90 C
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Examiner Edward P. Mazyck Examiner N/A Level: II Date: 03-10-2011 Level:
Date:
Sign: &
Sign:
AREVA Review: Dan Langenfeld Level: I Dat: 03-13-2011 Sign:
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